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[en] A thorium fuel cycle of a power plant controlled by accelerators was shown to be able to ensure safe and ecologically non-polluting generation of atomic energy. Suggestions on safe and ecologically non-polluting generation of electric power on the basis of a thorium fuel cycle are discussed. 11 refs., 1 fig
[en] The technique of evaluation of the multiplication factors and reactivity characteristics of fast reactors operating in the mode of multiple refueling is presented. We describe and apply the calculation method. The results demonstrate that fuel composition comes into equilibrium concentration in the multiple refueling reactor operation mode. If initial loads were based on plutonium from spent fuel of thermal and fast power reactors, equilibrium was achieved with twice repeated refueling. For initial fuel loads based on highly enriched uranium nitride or uranium-plutonium nitride fuel with high enrichment of 239Pu, equilibrium is reached after 4-5 refuelings
[en] The thorium-uranium fuel cycle has several advantages that make it attractive. Some of these beneficial properties are of particular interest now as they help alleviate current concerns. The Th-U cycle has neutronic advantages when utilized in thermal or epithermal reactors. Some of these reactors enjoy extraordinary safety qualities. The combination of these traits suggest that now is an appropriate time to deploy and begin exploiting the Th-U fuel cycle
[en] The paper deals with the evaluation of fuel handling in fast reactors in the closed nuclear fuel cycle. To solve these problems, the REPRORYV program code has been developed. It simulates the nuclide streams in out-of-reactor stages of the closed fuel cycle. Existed verified code JARFR is used for the calculation of neutron-physical characteristics of the core. Various options for nuclide streams are considered with a representative full-scale model of a fast reactor with sodium-cooled high-power. The changes of multiplication factor and mass of plutonium in the closed nuclear fuel cycle for a Russian BN-type fast reactor with use of the REPRORYV code are evaluated. Different scenarios of fuel reprocessing assuming the removing or retaining of actinides, taking into account various plutonium losses on reprocessing steps were considered. The questions of influence of the initial content of plutonium in nitride fuel (Pu-U-N) and the impact of the initial parameters to the possibility of fuel self-sufficient mode of the reactor during the whole period of its operation are studied
[en] In this meeting we will continue the established tradition to inform each other about the most important achievements of both projects and results of activities identified on last meeting which include areas of Proliferation Resistance, Economics, Safety, and Non-electric applications. We are also expecting discussion of new areas of potential cooperation such as Modelling and Simulation, SMRs, Institutional innovations, Advanced fuel cycles including Thorium, advanced materials, and Education and Training.
[en] To reply the huge world energy/ecological demand in the next century, a simple and rational Th energy system has been proposed, which is acceptable in public not only solving all issues relating with safety, nuclear-proliferation and -terrorism, radio-waste and breeding fuel-cycle, but also not requiring any big R and D cost and time. (author)
[en] This paper reports the results of nine structural lattices obtained through the WIMS-TRACA computer program. This work was performed by request of the managers of the WLU/IAEA project, for the extension of the first stage. These benchmark lattices include regular arrays with heavy water and data of the thorium cycle. Besides K∞ and Keff (employing the experimental buckling to account for the leakages) spectrum index and ratio at reaction rates are also determined for comparison with the experimental values. The input data for each lattice, are given in the appendix to help exploring possible differences in the results. (author). 4 refs, 1 fig, 11 tabs
[en] Summary: • Development of the next version of G4ECONS is progressing well; • Comparable results obtained from the benchmarking of G4ECONS, HEEP and H2A for hydrogen production; • Completed benchmarking G4ECONS with NEST in collaboration with IAEA: –Once-through SCWR; – Two fast reactors with closed fuel cycle.
[en] Experimental reactor physics is an essential element of physics design of a nuclear reactor and plays an important role in the safe design and operation of nuclear reactors. Approximations in modelling the reactor using computer codes and the ‘uncertainty in the nuclear data’ that goes as input into these codes contribute to the uncertainty of the theoretically computed design parameters. Reactor physics experiments provide estimates of the uncertainty in the design by comparing the measured and computed values of these parameters. A thorium fuel cycle based advanced heavy water reactor (AHWR) is being designed in Reactor Physics Design Division, BARC. A zero power critical facility (CF) was commissioned to generate the experimental data for physics design validation of AHWR. A number of experiments were carried out in CF which includes the measurement of differential/integral parameters and various reaction rates. The covariance analysis of these measurement will be carried out to generate the relevant covariance matrices
[en] The analysis of a nuclear power (NP) potential of a long term toxicity risk reduction has been conducted, considering current demands to NP for waste reduction. Neutronics intercomparison of both Uranium and Thorium fuel cycles with different neutron spectra in critical reactors and sub-critical systems allows to confirm a sufficient neutronics potential to reduce essentially both the fuel waste toxicity and fission products long term toxicity. An intrinsic potential of toxicity reduction for all important heavy nuclides in different nuclear systems is presented. This analysis has been used to indicate the potential role of ADS in different scenarios of nuclear power development. 8 refs., 2 figs., 3 tabs